Abstract
Dosimetry system DS86 included detailed calculations of gamma ray dose in individual samples (bricks and tiles) from Hiroshima and Nagasaki that had been measured by thermoluminescence (TL). Measurers took samples from superficial surfaces with a direct line of sight to the bomb, to get doses close to the kerma received by an infinitesimal sample suspended one meter above flat ground ("free-in-air (FIA) kerma"), but the actual in situ/FIA ratio varies. DS86 calculated in situ doses by adjoint Monte Carlo for models of samples and buildings in which they were located, but DS02 lacked resources for new calculations of this type. Therefore we analyzed the ratios calculated for DS86 and developed a method to apply them to the new gamma ray and neutron fluences of DS02 (samples calculated in DS86), and to choose the best estimates for new measurements (samples not calculated in DS86). We explain the DS02 methods and summarize the results. Agreement is good overall and somewhat improved over DS86 in Hiroshima. [J Radiat Res 44:383-384 (2003)]